High heat flux testing of 12-14Cr ODS ferritic steels

The thermal performance of Fe-(12-14)Cr-2W-0.3Ti-0.3Y(2)O(3) ODS reduced activation ferritic steels, which are considered as candidate first wall materials for the future fusion power reactors and were manufactured by mechanical alloying in hydrogen and hot isostatic pressing, was assessed by high heat flux (HHF) testing with the electron beam JUDITH facility at the Forschungszentrum Julich (FZJ), Germany. An analysis of the microhardness and microstructure of the specimens was done before and after HHF tests.

High heat flux testing of 12-14Cr ODS ferritic steels

Graph Chatbot

Innovative thermophysical characterization of an ATF composite cladding: the case of silicon carbide

Plasmoid drift and first wall heat deposition during ITER H-mode dual-SPIs in JOREK simulations

Thermal conductivity of Li 3 PS 4 solid electrolytes with ab initio accuracy

Innovative thermophysical characterization of an ATF composite cladding: the case of silicon carbide

Plasmoid drift and first wall heat deposition during ITER H-mode dual-SPIs in JOREK simulations

Thermal conductivity of Li 3 PS 4 solid electrolytes with ab initio accuracy